ML20054M840
| ML20054M840 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 07/01/1982 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20054M841 | List: |
| References | |
| NUDOCS 8207150032 | |
| Download: ML20054M840 (5) | |
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DUKE POWER COMPANY DOCKET NO. 50-369 f1CGUIP.E !!UCLEAR STATION, UNIT 1 AMEllDCHT TO FACILITY OPERATIt'G LICENSE Acendment No.14 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the !!cGuire Huclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Coopany (licensee) dated June 9,1982, complies with the standards and requirements of the Atoraic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFP, Chapter I; 8.
The facility will operate in confomity with the application, the provisions of tbc Act, and the regulations of the Commission; C.
There is reasonable assurance: (1) that the activities authorized by this amendnent can be conducted without endangering the health and safety of tne public, and (ii) that such activities will be i
conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license anendnent will not be inimical to the comon defense and security or to the health and safety of the public; E.
The issuance of this amendaent is in accordance with 10 CFR Part 51 of the Connission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amend: ent and paragraph 2.C.(2) of Facility Operating License !!o. NPF-9 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Arendment Ho.14, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8207150032 820701 OF'N PDR ADOCK 05000369
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This license a.mende.ent was effective June 9,1982.
FOR THE HUCLEAR F.ECULATORY COM11SS10M
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Elinor G. Adensan, Chief Licensing Branch flo. 4 laivision of Licensing i
Attachment:
Technical Specification Changes Date of Issuance: July 1, 1982 1
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ATTACHiO1T TO LICE!)SE A*DiDMEliT i:0. 14 FACILITY OPEl'ATIt!C LICEllSE ?!0. f:PF-9 DOCKET fl0. 50-369 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revise't pages are identified by Anendment nunber and contain a vertical line indicating the area of change. The corresponding overlecf pages are also provided to naintain docmcent co9pleteness.
Overleaf Anended Pane Paqe 3/4 5-6 3/4 5-5 l
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OFFICIAL RECORD COPY UMN.1981-335-963 NRC FORM 318 (1C
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EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - T greater than or equal to 350 F avg
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LIMITING 'ONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:
l' a.
One OPERABLE centrifugal charging pump, i
b.
One OPERABLE safety injection pump, c.
One OPERABLE residual heat removal hcat exchanger,*
d.
One OPERABLE residual heat removal pump, and An OPERABLE flow path capable of taking suction from the refueling e.
water storage tank on a safety injection signal and automatically transferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
.l l
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN.tithin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
i b.
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation cycles to date.
The current value of the usage factor for each affected safety injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.
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- For a period of 3 days commencing on June 9, 1982 and running through 9:00 a.m.
June 12, 1982, the seismic support system associated with this heat exchanger may be INOPERABLE.
l McGUIRE - UNIT 1 3/4 5-5 Amendment No. 14 l
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the following valves a.
are in the indicated positions with power to the valve operators removed:
Valve Number Valve Function Valve Position a.
INI162A a.
Cold Leg Recirc.
a.
Open b.
1 nil 21A b.
Hot Leg Recirc.
b.
Closed c.
INIl528 c.
Hot Leg Recirc.
c.
Closed d.
1NI1838 d.
Hot Leg Recirc.
d.
Closed e.
INI173A e.
RHR Pump Discharge e.
Open f.
INIl788 f.
RHR Pump Discharge f.
Open g
INIl008 g.
Open l
h.
1FW27A h.
RHR/RWST Suction h.
Open l
i.
INIl47A i.
SI Pump Mini flow i.
Open b.
At least once per 31 days by:
1.
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points,
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and 2.
Verifying that each valve (manual, power operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position.
By a visual inspection which verifies that no loose debris (rags, c.
trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of each containment entry when C0"TAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
Verifying automatic isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 560 psig.
McGUIRE - UNIT 1 3/4 5-6 JUN 1981 t
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